Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants (open access)

Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Foreword: This report describes the results of a series of engineering evaluation studies conducted between July 1, 1961 and June 30, 1962, related to heavy water moderated power reactor plants.
Date: June 30, 1962
Creator: Chittenden, W. A. & Hoveke, G. F.
Object Type: Report
System: The UNT Digital Library
Investigations of Radioactive Fuel-Bearing Glasses (open access)

Investigations of Radioactive Fuel-Bearing Glasses

"A series of high urania-content glasses were fiberized and examined for high-temperature strength properties. One glass, RX360 containing 60% U/sub 3/O/ sub 8/ by weight, had better high-temperature tensile properties than any glass previously reported. It was observed that many of the glasses studied separated into immiscible phases and that the fiberizable glass phase had lower U/sub 3/O/ sub 8/ content than the base compositions. A physical analysis of crystal structures of the devitrification products from the nuclear fuel glasses indicated that most of the crystals consisted of uranium oxide in a reduced state. By adding O/sub 2/ to molten glass, it was possible to eliminate most of this devitrification. By elimination of crystals, the fiberizing of the glass was more uniform and the glasses produced had more consistent physical properties."
Date: June 30, 1962
Creator: Lockwood, P. A.
Object Type: Report
System: The UNT Digital Library
Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962 (open access)

Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962

S>Progress is reported on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant. The topics covered include: fuel material cladding, bonding, and irradiation testing; heat transfer and fluid flow; fuel element manufacturing research and development; low-enrichment superheater fuel element design; mechanical studies of control rods, guide tubes, and control rod drives; reactor physics; and reactor and system dynamics. (C.H.)
Date: June 30, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Annotated Bibliography on Soft X-ray Spectroscopy (open access)

Annotated Bibliography on Soft X-ray Spectroscopy

Report presenting a bibliography of about 550 references of the soft X-ray literature since 1950 and through 1960. The emphasis is on the application of soft X-ray spectroscopy to the study of valence band electronic states in metals and alloys. Therefore, the spectral region of 25 to 800 angstroms involving ruled glass grating spectrometers is of principal interest. In addition to soft X-ray data, references on all pertinent aspects of the apparatus and experimental problems are included. Also listed separately are references of value in corroborating soft X-ray data with other results. Subject, author, X-ray band, material, and other indices are included.
Date: June 29, 1962
Creator: Yakowitz, Harvey, 1939- & Cuthill, J. R.
Object Type: Report
System: The UNT Digital Library
Chemical Processing Technology Quarterly Progress Report, January-March 1962 (open access)

Chemical Processing Technology Quarterly Progress Report, January-March 1962

The processing of Al fuel, principally of the MTR-ETR type, is reported. Processing rate averaged 90% of flow sheet values for the entire operating period, and a U recovery of 99.85% was achieved. Aqueous Zr fuel processing studles continued with the objective of adapting the HF process to continuous dissolution-complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Good results were indicated in a 190-hr run dissolving 2% U-Zr fuel in a Monel dissolver using 4.8M HF-0.03M HNO/sub 3/ dissolvent at 200 deg F; insoluble material did not accumulate in the dissolver, although a U-containing film was formed, apparently in small, equilibrium quantity. Shorter term continuous laboratory dissolutions indicated that 4.8M acid was preferable to 10M acid for the acid feed rate/fuel surface ratios proposed, resulting in dissolver products of greater stability and higher uranium content. Additional laboratory data are presented on UF/sub 4/ hydrate form and solubility, together with maximum dissolvable U compositions with Zircaloy under various flowsheet condltions. Processing of Al alloys containing high Si was found to present no unusual problems in laboratory studies. Siliceous residues resulting from dissolution of Al-U alloys containing 2% …
Date: June 29, 1962
Creator: Bower, J. R.
Object Type: Report
System: The UNT Digital Library
Direct Contact Condensation With Two Immiscible Fluids (open access)

Direct Contact Condensation With Two Immiscible Fluids

87p. The theory, design techniques, and relative economics are presented for three basically different direct-contact condensation processes involving fluids whose condensed phases are immiscible. In the specific system developed for the study, Aroclor 1248 (Monsanto Chemical Corporation) and steam were used. The processes investigated include the injection, and the induction of steam into a highvelocity stream of Aroclor in the throat section of a Venturi. The bubbling of steam into a low-velocity stream of Aroclor, using a packed tower to artificially increase the surface of contact was also investigated. The induction, injection, pressure drop, and heat-transfer characteristics of a Venturi in direct-contact condensation service were experimentally investigated, and empirical correlations for the performance of the unit are included. The performance of a direct-injection device was also experimentally determined, and correlations obtained. A discussion is included concerning the theoretical development of relations which are used to predict the performance of packed towers in direct-contact condensation service. (auth)
Date: June 29, 1962
Creator: Lackey, D. L.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
FEASIBILITY STUDY FOR INPLACE ANNEALING OF THE PM-2A REACTOR VESSEL (open access)

FEASIBILITY STUDY FOR INPLACE ANNEALING OF THE PM-2A REACTOR VESSEL

None
Date: June 29, 1962
Creator: Medal, E.
Object Type: Report
System: The UNT Digital Library
Improved Sample Bonding and Emission With Tantalum Surface Ionization Filaments (open access)

Improved Sample Bonding and Emission With Tantalum Surface Ionization Filaments

Techniques for conditioning of Ta filaments for improved bonding and emission with a Ta metal powder-Ta/sub 2/O/sub 5/ mixture are described. A porous Ta metal layer is deposited which restricts sample to the filament. Metal- oxide ion emission is enhanced with additional Ta/sub 2/O/sub 5/ to the porous layer. Reduction of fractionation through action of liquid Ta/sub 2/O/sub 5/ is discussed in particular for Sr+ emission. Use of conditioned filaments for rapid U concentration analysis with a single-filament mass spectrometer is emphasized. (auth)
Date: June 29, 1962
Creator: Goris, P.
Object Type: Report
System: The UNT Digital Library
MOUND LABORATORY PROGRESS REPORT FOR JUNE 1962 (open access)

MOUND LABORATORY PROGRESS REPORT FOR JUNE 1962

Research and development progress is reported on plastics, analytical methods, radioelements, isotope separation and purification, reactor fuels and materials developmert, Ranger x-ray sensor program, and SNAP a. (M.C.G.)
Date: June 29, 1962
Creator: Grove, G.R.; Jones, L.V. & Eichelberger, J.F.
Object Type: Report
System: The UNT Digital Library
Organic Coolant Reactor Program Quarterly Report, January 1-March 31, 1962 (open access)

Organic Coolant Reactor Program Quarterly Report, January 1-March 31, 1962

The possible effects of a hydrogen atmosphere in reducing film deposition were studied in the large circulating loop and in rocking cell and pyrolytic capsule tests. At H/sub 2/ pressures of 200 to 400 psig no reduction in film weight deposited was observed in the loop tests, and in the pyrolytic tests film deposits were doubled. Heat conductivity of the films was much higher however. ln these high ash films the inorganic constituent was found to be alpha -Fe rather than the usual magnetite, which seems to account for the heat conductivity. Separation of benzene-insoluble material from high boiler and coolant was accomplished by centrifugation and by deposition on glass. The material was closely related to film formation. The nature of the inorganic and organic constituents of this material was examined in several analytical studies. Advances in the techniques of nuclear magnetic resonance, O/sub 2/ analysis, measurement of chromatograms, application of computers, and other methods were made. It was demonstrated by use of Fe5/sup 59/ that irradiated terphenyl under air attacks Fe rapidly and possibly the Fe is in solution as a chelate or other complex. It also was indicated by some tests that such a soluble form of Fe …
Date: June 29, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-1369 (open access)

Texas Attorney General Opinion: WW-1369

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Mose A. Gimbel's Estate.
Date: June 29, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-1372 (open access)

Texas Attorney General Opinion: WW-1372

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether a district judge may assess as court costs an investigator's fee for the investigation required by Article 46(a), Section 2, Vernon's Civil Statutes.
Date: June 29, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Thermal Analysis of SM-1 Core III (open access)

Thermal Analysis of SM-1 Core III

Abstract This technical report covers the thermal analysis performed on the SM-1 Core III for both steady state and transient conditions is reported. SM-1 Core III will be used as a test for Type 3 elements in a PM-2A Core. The steady state analysis indicated minimum departure from nucleate boiling ratios (DNBR) for both design and scram conditions above the minimum criteria of 1.5. Local nucleate boiling was noted in the hot internal channels and lattice passage at scram power conditions. Loss of flow transient results indicate DNBR's above 1.5, insuring that the core is safe from burnout. Bulk boiling was noted in the hot channels and lattice passage at scram power condition.
Date: June 29, 1962
Creator: Davidson, S. L.
Object Type: Report
System: The UNT Digital Library
Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program, Program Summary and References (open access)

Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program, Program Summary and References

This is one of twenty-one volumes sumarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume discusses the background to the General Electric program, and summarizes the various direct-air-cycle nuclear test assemblies and power plants that were developed. Because of the requirements of high performance, low weight, and small size, vast improvements in existing technology were required to meet the flight objectives. The technological progress achieved during the program is also summarized. The last appendix contains a compilation of the abstracts, tables of contents, and reference lists of the other twenty volumes.
Date: June 28, 1962
Creator: Thornton, G. & Rothstein, A.J.
Object Type: Report
System: The UNT Digital Library
Primary Shield Optimization Survey for the PL-3 Reactor (open access)

Primary Shield Optimization Survey for the PL-3 Reactor

A detailed study of four reactor and shield configurations was made. Two basic reactor types, the boiling water and pressurized water reactors were considered. Shield materials of lead-water and iron-water were used with varying thicknesses for determining the optimum shield configuration for the PL-3 reactor. Also presented is a survey of available shielding codes. (auth)
Date: June 28, 1962
Creator: Scoles, J. F. & Crouch, A. N.
Object Type: Report
System: The UNT Digital Library
A Review of Hanford Power Level Limits (open access)

A Review of Hanford Power Level Limits

As for any nuclear reactor, the operation of the Hanford reactors is governed by many technical and administrative considerations. With the completion of current project action, later this year, certain of the technical limitations on reactor power level will be relieved, notably at the K Reactors, At that time, the technical and engineering limitations will be more liberal at some reactors than required for operation at the administrative power level limits, imposed by the Atomic Energy Commission, that are currently in force. The following report discusses the various technical factors governing reactor power levels and compares these with the currently imposed administrative power level limits.
Date: June 28, 1962
Creator: Van Wormer, F. W.
Object Type: Report
System: The UNT Digital Library
VELOCITY DISTRIBUTIONS IN A SNAP REACTOR COOLING CHANNEL. Thermo-Physics Technical Note No. 2 (open access)

VELOCITY DISTRIBUTIONS IN A SNAP REACTOR COOLING CHANNEL. Thermo-Physics Technical Note No. 2

Methods for determining the velocity distributions in a SNAP reactor coolant channel for both laminar and turbulent flow conditions are presented. The results obtained by applying the methods to SNAP-2 conditions are given as maps of the ratio of local velocity to average velocity in the coolant channel. The use of the velocity distributions in subsequent heat transfer analyses of the fuel rod and coolant system is discussed. (auth)
Date: June 28, 1962
Creator: Fields, S. R.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-1366 (open access)

Texas Attorney General Opinion: WW-1366

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Construction of Item 5 of the appropriation to the Game and Fish Commission.
Date: June 27, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-1367 (open access)

Texas Attorney General Opinion: WW-1367

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the Texas Water Commission is required to pay the costs of publication of notice of hearing.
Date: June 27, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-1368 (open access)

Texas Attorney General Opinion: WW-1368

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Does a Commissioners Court have the authority to establish a public road under Article 6711, V.C.S., if the applicant for said road resides on the land into which there is now no public road or public access?
Date: June 27, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Thermal Stress Testing of Type 1 Fuel Plates (open access)

Thermal Stress Testing of Type 1 Fuel Plates

Thermal stress tests on Type 1, SM-1A Core II fuel ele-ment sections were performed to study plate distortion and determine its dependency on temperature distribution, temperature differential, initial flatness, and ripple length. Test results will be correlated with the analytical model and used to predict ripple growth in other plate-type fuel elements. The tests showed that ripple growth is dependent on initial flatness of the plate and that the characteristic shape of ripples is maintained at all temperature differentials: The tests also showed that the ripple growth rate for a ripple of 5 mil initial magnitude is approximately 0.12 mils/ deg F for a peak temperature differential of 103 deg F and that the apparent relationship between ripple net growth and length is 1.3 mil/in. of ripple for a peak temperature differential of 103 deg F. A permanent distortion of 2 mils for a complete temperature cycle from 0 to 103 to O deg F differential was found. The temperature profile across the plate width was found to affect the magnitude of ripple growth. (auth)
Date: June 27, 1962
Creator: Gebhardt, F. G.
Object Type: Report
System: The UNT Digital Library
The Fast Rise Pulser (open access)

The Fast Rise Pulser

A circuit is described developed to fill the need for a pulser with a 15-20 volt amplitude into the 93 ohm line, stable, transistorized and low cost, fast 10 Nano second rise, and a variable repetition period from 0.5 sec. to 4 sec.
Date: June 26, 1962
Creator: Kiriokos, George
Object Type: Report
System: The UNT Digital Library
Technical criteria and bases for a Zirconium-tubed K Reactor (open access)

Technical criteria and bases for a Zirconium-tubed K Reactor

The criteria contained in this report have been established to provide the technical bases for the design modifications involved in the K-Reactor tube replacement. The ultimate intent of these criteria is to provide the basic technical data and concepts to assure: (1) technical feasibility and operability of the reactor system as modified, (2) operation of the reactor and its services to minimize nuclear and radiation hazards, and (3) appropriate lifetime of the reactor and its service facilities as modified. The criteria are appropriately broad and may not contain all the data necessary to accomplish detail design. The information contained herein shall serve as a basis for evaluation and approval of all portions of the modification relating to the process as indicated in the above three points.
Date: June 26, 1962
Creator: Curtiss, D. H.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-1356 (open access)

Texas Attorney General Opinion: WW-1356

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Local option election under Art. 666-32, P.C.; questions pertaining to the petition.
Date: June 26, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History